ML19256E840
| ML19256E840 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/07/1979 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19256E838 | List: |
| References | |
| NUDOCS 7911150362 | |
| Download: ML19256E840 (46) | |
Text
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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY '
6.1.1 The General Manager shall be responsible for over.111 facility l operation and shall delegate in writing the succession to this responsi-oility during his absence.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2.1-1.
, FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figures 6.2.2 1 and 6.2.2-2 and:
- a. Each on duty shift shall be composed of at least the mininum shif t crew comoosition shown in Table 6.2.2-1.
- b. At least one licensed Operator shall be in the control room for each reactor containing fuel,
- c. At least two licensed Operators shall be present ir. the control room for each reactor in the process nf start-up, scheduled reactor shutdown and during recovery from rsactor trips.
- d. An individual qualified to implement radiation protection procedures shall be on site when fuel is in either reactor.
- e. All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent respon-sibilities during this operation.
- f. A Fire Brigade of at least five members shall be maintained onsite at all times. The Fire Brigade shall not include the minimum shift crew shown in Table 6.2.2-1 or any personnel required for other essential functions during a fire emergency.
1333 190 BRUNSWICK-UNIT 1 6-1 7 91115 0j36 2L;
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CHAfru.iN OF THE BOARD PRESIDENT / CHIEF EXECUTIVE OFFICER OPERATIONS Senior ExecQice Pres. _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ ,
Chief Operating Officer l 1
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POWER SUPPLY I AND 8 CUSTOMER SERVICES '
Executive Vice Presicent i
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POWER SUPPLY I Senior Vice President l
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NUCLEAR OPERATIONS NUCLEAR SAFETY ',
DEPARTMENT ~AND Vice President RESEARCH Vice President l 1
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I NUCLEAR OPERATIONS CORPORATE NUCLEAR SAFETY I DEPARTMENT AND I 3 ,99 's , QUALITY /SSURANCE AUDIT J s ,. Nanager N i
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i Plant i
-J General Manager a
I Plant Nuclear j} }Qj
- Responsible for performance Safety and monitoring of Fire Comi ttee Protection Program.
MANAGEMENT ORGANIZATION CHART BRUNShlCK - UNIT I FIGURE 6.2.1-1 6-2
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BRUNSWICK-UNIT 1 6-3 1335 182
~~ ~ PLANT GENERAL MANAGER , , DIRECTOR Nuclear Safety ana Quality Assurance , SUPERVI SOR SPEClAllSTS SUPERVISOR Quality Fire Protection Training Assurance FIRE PROTECTION FIRE PREVENTION SUPPORT GROUP COMMITTEE BRIGADE FI RE CHI EF* ' (EMERGENCY COORDIN ATOR)
, SHI FT FI RE '
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- Number of Brigace Fire Chief s varies with shif t organization '
" One Specialist is assigned the duties of the p'lant fire chief FIGURE 6.2.2-2 ./
BRUNSWICK - UNIT I } 33b '} 83 6-4
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ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the mini-mum qualifications of ANSI N18.1-1971 for comparable position, except fcr the Environmental and Radiation Contrel Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. l 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be m8intained under the direction of the Training Supervisor and shal'l meet Or exceed the requirements and recommendations of Section { 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55. 6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Plant Fire Chief and shall meet or exceed the require-ments of Section 27 of the NFPA Code-1975. 6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY COMMITTEE (PNSC) FUNCTION 6.5.1.1 The PNSC shall function to advise the General Manager on all matters related to nuclear safety. (- COMPOSITION 6.5.1.2 The PNSC shall be composed of the: Chairman: Plant General Manager y erations Manager, Maintenance Manager, Vice Chairman: Technical-Administrative Manager, or Director-Nuclear Safety and QA Secretary: Administrative Supervisor Member: Maintenance Supervisor (I&C) Member: Maintenance Supervisor (Mechanical) l Member: Engineering Supervisor Member: Environmental and Radiation Control Supervisor Member: Quality Assurance Supervisor Member: Shift Operating Supervisors Member: Training Supervisor A.TERNATES 6.5.1.3 All alternate memoers shall be appointed in writing by 1.he PNSC Chairman to serve on a temporary basis; however, no more than two alternate's shall participate as voting members in PNSC act vities at any one time. BRUNSWICK-UNIT 1 6-6 } 3 3,I) ) 8 s{
ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The PNSC shall meet at least once per calendar month and as convened by tha PNSC Chairman or his designated alternate. QUORUM 6.5.1.5 A quorum of the PNSC shall consist of the Chairman or Vice Chairman and three members including alternates. RESP 0NSIBILITIES 6.5.1.6 The PNSC shall be responsible for:
.a . Review of 1) all procedures required by Specification 6.3 and changes thereto, 2) any other proposed procedures or changes thereto as determined by tne General Manager to affect nuclear safety. (
- b. Review of all proposed tests and experiments that affect nuclear saf ety.
- c. Re, view of all proposed changes to Technical Specifications.
- d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
- e. Investigation of all violations of t..e Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President - Nuclear Operations and to the Manager - Corporate Nuclear Safety ar.d Quality Assurance Audit,
- f. Review of all events requiring 24 hour notification to the Commission.
- g. Review of facility operations to-detect potential safety hazards.
- h. Performance of special reviews, investigations and reports thereon as requested by the Manager - Corporate Nuclear Safety and Quality Assurance Audit.
BRUNSWICK-UNIT 1 67 1335 185
ADMIIISTRATIVE CottTROLS RESPONSIBILITES (Continued) ; i. Review of the Plant Security Plan and irr lementing procedure:. j. Review of the Emergency Plan and implementing procedures. AUTHORITY 6.5.1.7 The PNSC shall:
- a. Recommend to the General Manager written approval or disapproval of items considered under 6.5.1.6(a) through (d) above. l
- b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.
c. Provide written netification within 24 hours to the Vice President-Nuclear Operations and the Manager - Corporate Nuclear Safety arl Quality Assurance Audit of disagreement between the PNSC and the General Manager; however, the General Manager shall have responsibility for resolution of och disagreements pursuant to 6.1.1 above. RECORDS 6.5.1.8 The PNSC shall maintain written minutes of each meeting and I copies shall be provided to the Vice President-Nuclear Operations and to the Manager - Corporate Nuclear Safety. and Quality Assurance Audit. 1335 186 BRUNSWICK-utili 1 68
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. ADMINISTRATIVE CONTROLS 6.5.2 Corporate Nuclear '{ety & Ouality Assurance Audit Section (CNS & OAAS)
- Responsibility i 6.5.2.1 The Manager - Corporate Nuclear Safety & Quality Assurance Audit under the Vice President-Nuclear Safety and Research is charged with the overall responsibility for administering the independent off-site review and quality assurance audit programs as follows:
- a. Approves selection of the individual (s) to conduct off-
;- site safety reviews and quality assurance audits.
- b. lias access to the plant operating records and operating personnel in performing the independent reviews and quality assurance audits.
- c. _ Prepares and retains written records of reviews and audits.
- d. Assures independent safety reviews are conducted on all items required by Section 6.5.3.3 and quality assurcnce audits cover all the items included in Section 6.5.4.1.
- e. Distributes reports and other records to appropriate managers.
t 6.5.3 Corporate Nuclear Safetv Unit 1335 187 Function BRUNSWICK-UNIT 1 6-9 -
_ . . ____ ___ >__ _ .a . ._ _ - -- ACHINISTRATIVE CONTROLS 6.5.3.1 The Corporate Nuclear Safety Unit of the Corporate Nuclear Safety & Quality Assurance Audit Section shall provide independent off-site review of significant plant changes, tests, and procedures; verify that reportable occurrences are promptly investigated and corrected in a manner which reduces the probability of recurrence of such events; and detect trends which nay not be apparent to a day-to-day observer. Personnel 6.5.3.2
- a. Personnel assigned responsibility for independent reviews shall be specified in technical disciplines, and shall collec-tively have the experience and competence required to review problems in the following areas:
- 1. Nuclear power plant operations
- 2. Nuclear engineering
- 3. Chemistry and. radiochemistry
- 4. Metallurgy
- 5. Instrumentation and control
- 6. Radiological safety
- 7. Mechanical and electrical engineering
- 8. Administrative controls
- 9. Seismic and environmental
- 10. Quality assurance practices
- b. The following minimum experience requirements shall be es-stablished for those persons involved in the independent off-site safety review program:
BRUNSWICK-UNIT 1 6-10 -
ADMINISTRATIVE CONTROLS _ _ _ .
- 1. Manager of CNS & QAAS - Bachelor of Science in engineering or related field and ten (10) years related experience including five (5) years involvement with operation and/or design of nuclear power plants. ~
- 2. Reviewers - Bachelor of Science in engineering or related field or equivalent and five (5) years related experience including three (3) years involvement with operation and/or design of nuclear power plants.
- c. An individual may possess competence in more than one specialty area. If sufficient expertise is not available within the Corporate Nuclear Safety Unit, competent individuals from other CP&L organizations or oucside consultants shall be utilized in performing independent off-site reviews and investigations.
- d. At least three persons, qualified as discussed in Specifica-tion 6.5.3.2.b, will review each item submitted under the
, ._ requirements of 6.5.3.3.
- e. Independent safety reviews shall be performed by personnel not directly involved with the activity or responsible for the activity.
Subj ects Requiring Independent Review 6.5.3.3 The following subjects shall be reviewed by the Corporate Nuclear Safety Unit: i 6-11 BRUNSWICK-UNIT 1
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. ADMINISTRATIVE CONTROLS _
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- a. Written safety evaluations of changes in the facility as described in the Safety Analysis Report, changes ir procedures as described in the Safety Analysis Report and tests or experi-ments not described in the Safety Analysis Report which are completed without prior NRC approval under the provisions of 10 CFR 50.59(a)(1) . This review is to verify that such changes, tests, or experiments did not involve a change in the technical specifications or an unreviewed safety question as defined in 10 CFR 50.59(a)(2),
- b. Proposed changes in procedures, proposed changes in the facility, or proposed tests or experiments, any of which involves a change in the technical specifications or an unreviewed safety ques-tion pursuan* to 10 CFR 50.59(c) . Matters of this kind shall be refere co the Corporate Nuclear Safety Unit by the Plant Nucir 'afety Committee following its review, or by other functional organizational units within Carolina Power & Light Company (CP&L) prior to implementation.
- c. Changes in the technical specifications or license amendments relating to nuclear safety prior to implementation, except in those cases where the change is identical to a previously reviewed proposed change.
- d. Violations, deviations and reportable events, which require reporting to the NRC within 24 hours, and as defined in the plant technical specifications such as:
- 1. Violations of applicable codes, zegulations, orders, technical specifications, license requirements or internal procedures or instructions having safety significance; and
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BRUNSWICK-UNIT 1
. AD:11NIST1MTIVE CONTROLS
- 2. Significant operating abnormalities or deviations from normal or expected performance of plant safety-related structures, systems, or components.
Review of events covered under this paragraph shall include the results of any investigations made and the recommendations resulting from such investigations to prevent or reduce the probability of recurrence of the event.
- e. Any other matter involving safe operation of the nuclear power plant which the Manager - Corporate Nuclear Safety
& Quality Assurance Audit Section deems appropriate for consideration, or which is referred to the Manager -
I' Corporate Nuclear Safety & Quality Assurance Audit Section by the onsite operating organization or by other functional organizational units within Carolina Power & Light Company. Follow-un Action 6.5.3.4 Results of Corporate Nuclear Safety (CNS) reviews, including recommendations en.d concerns will be documented.
- a. Copies of the documented review will be retained in the Corporate Nuclear Safety & Quality Assurance Audit Section files.
b. Recommendatlans and concerns will be submitted to the Vice President - Nuclear Operations within 14 days of determination.
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- c. A summation of Corporate Nuclear Safety recommendations and concerns will be submitted to the President /i!hief Executive BRUNSWICK-UNIT 1 6-12a 1335 I9I
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Officer; Senior Executive Vice President and Chief Operating Officer; Executive Vice President-Power Supply and Customer Services; Senior Vice President-Power Supply; Vice President-Nuclear Safety and Research; Plant General Manager; and others, as appropriate on at least a bi-monthly frequency. , 6.5.3.5 The Corporate Nuclear Safety Unit review program shall be conducted in accordance with written, approved procedures. s 6.5.4 Operation & Maintenance Unit Function 6.,5.4.1 The Operation & Maintenance Unit of the Corporate Nuclear Safety & Quality Assurance Audit Section shall perform audits of plant activities. These audits shall encompass:
- a. The conformance of facility operation to all provisions
, _ contained within the Technical Specifications and applicable license conditions at least once per year.
- b. The training and qualifications of the entire fac .ity staff at least once per year,
- c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or method of operation that affect nut. lear safety at least once per six months.
- d. The verification of compliance and implementation of the requirements of the Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per two years.
BRUNSWICK-UNIT 1 6-12b l } } r~) Jg
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. . ADMNISTRATTVr CONTROLS . -
- e. The Emergency Plan and implementing procedures at least once per two years. _ _ _ _ _ .
- f. The Security Plan and implementing procedures at least once per two years.
- g. The Facility Fire Protection Program and implementing procedures at least once per two years.
- h. Any other area of facility operation considered appropriate by the Corporate Quality Assurance Audit Operation 6 Main-tenance Unit, the Executive Vice President-Power Supply and Customer Services, or the Senior Vice President-Power Supply.
Personnel 6.5.4.2
- a. Audit personnel will be independent of the area audited.
Selection for auditing assignments is based on experience or training which establishes that their qualifications are commensurate with the complexity or special nature of the ac-
._tivities to be audited. In selecting auditing personnel, consideration will be given to special abilities, specialized technical training, prior pertinent experience, personal characteristics, and education,
- b. Qualified outside consultants or other indivi'uals inc ependent i from those personnel directly involved in plant operation, but within the Operations Groups will be ttsed to augment the audit teams when necessary. ,
1335 193 BRUNSWICK-UNIT 1 I 6-12e S
ADMINISTRATIVE CONTROLS p epc,r t s 6.5.4.3 Results of audit are approved by the Manager - Corporate Nuclear Safety & Quality Assurance Audit Section and transmitted directly to the Company President / Chief Executive Officer, the Senior Executive 71ce President and Chief Operating Officer, the Executive Vice President-I Power Supply and Customer Services, the Senior Vice President-Power Supply, and the Vice President-Nuclear Safety and Research, and others as appropriate, within 30 days after the completion of the audit. 6.5.4.4 The corporate quality assurance audit program shall be conducted in accordance with written, approved procedures. 6.5.5 0UTSIDE AGENCY INSPECTION AND AUDIT PROGRAM 6.5.5.1 An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utiliz1}ng an outside fire protection firm. 6.5.5.2 An inspection and audit of the fire protection and loss prevention program shall be performed by a ;ualified outside fire consultant at l least once per 36 months. BRUNSWICK-UNIT 1 6-13 - 133b 194
ADMINSTRATIVE CONTROLS 6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES: ,
- a. The Commission shall be notified and/or a report submitted '
pursuant to the requirements of Specification 6.9.
- b. Each REPORTABLE OCCURRENCE requiring 24 hour notification to the Commission shall be reviawed by the PNSC and submitted to Manager - Corporate Nuclear Safety and Quality Assurance Audit and the Vice President-Nuclear Ops.tations.
6.7 SAFtTY LidIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
- a. The facility shall be placed in at least HOT SHUTDOWN within two hours,
- b. The Saf ety Limit violation shall ta reported to the Commission, the Vice President-Nuclear Operations, and to the Manager-Corporate I Nuclear Safety and Quality Assurance Audit within 24 hours.
- c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PF"C. This report shall describe (1) applicable circumstances pi :eding the violation, (2) effects of the violation upon facility omponents, systems or struc-tures, and (3) corrective action taken to prevent recurrence.
- d. The Safety Limit Violation Report shall be submitted to the Commission, the Manager - Corporate Nuclear Sa fety and Quality Assurance Audit, and the Vice President-Nuclear Operations within 14 days of the violation.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and main-tained covering the activities referenced below:
- a. The applicable procedures recommended in Appendix "A" of Regulatory Cer;e 1.33, November,1972.
- b. Refueling operations.
- c. Surveillance and test activities of safety related equipment.
- d. Security Plan implementation.
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- e. Emergency Plan implementation,
- f. Fire Protection Program implementation. -
BRUNSWICK - UNIT 1 6-14 ' W N w-me e1 mmhe 6
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ADMINISTRATIVE CONTROLS PROCEDURES (Continued) 6.8.2 Each procedure of 6.8.1 above, and changes thereto, sh:11 be reviewed by the PNSC and approved by the General Manant prior to imple- l mentation and reviewed periodically by the PNSC as set forth in admin-istrative procedures. 6.8.3 Temporary changes to procedures r,f 6.8.1 above may be made provided:
- a. The intent of the original procedure is not altered.
- b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's Li. cense on the Brunswick Plant.
- c. The change is documented, reviewed by the pNSC and approved by the General Manager within 14 days of implementation.
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- 6.9 REPORTING REOUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES .
6.9.1 In addition to the applicable reporting requir:ements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspsetion and Enforcement unlets otherwise noted. STARTUp REPORT 6.9.1.1 A sumary report of plant startup and power escalation testin i shall be submitted following (1) receipt of an operating license, (2) g amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have significantly altered the nJclear, thennal, or hydraulic perfor-
- mance of the plant.
9 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test. pro-gram and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other corr: nit-ments shall be included in this report. 6.1.1.3 Startup reports shall be submitted within (1) 90 days follow-ing completion of the startup test program, (2) 90 days following re-sumption or commencement of commercial power operation, or (3) 9 months I following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e. , initial criticality, , BRUNSWICK - UNIT 1 6-15
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RECORD RETEjiTION (Continued)
- h. Records of annual physical inventory of all sealed source material of record.
6.10.2 The following records shall be retained for the duration of the Facility Operating License:
- a. Records and drawing changes reflecting facility design modifi-cations made to systems aho aquipment described in the Final Safety Analysis Report.
- b. Records pf new and irradiated fuel inventory, fuel transfers and asseably burnup histories,
- c. Records of facility radiation and contamination surveys.
- d. Records or radiation exposure fer all individuals entering radiation control areas.
- e. Records of gaseous and liquid ?adidactive material released to the environs.
- f. Records of transient or operational cycles for those facility components identified in Table So7.1-1.
- g. Records of reactor tests and experiments o
- h. Records of training and quali'ication for current members of the plant staff.
- i. Records of in-service inspectiere perforted pursuant to these lechnical Specifications.
J. Records of Quality Assurance activtties required by the QA Manual. '
- k. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
)* Records of meetings of the PNSC and of the previous off-site review organization, Company Nuclear Safety Committee (CNSC).
6.11 RADIATION PROTECTION PROGRAM Procedut es for peasonnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure. BRUNSWICK - UNIT 1 6-20 1335 197
Obiective This section describes the administrative c.mcrols and procedures necessary to implement the Environmental Technical Specifications. 5.1 ORGANIZATION AND REVIEW The General Manager is directly responsible for the safe operation of the l facility as shown in Figure 5.1-1. In all matters pertaining to the operation of the plant and to the Environmental Technical Specifications, the General Manager is directly responsible to the Vice President - Nuclear Operations. The Environmental and Radiation Control Supervisor is responsible to the General Manager for all Environmental Technical Specifications applicable to the plant, radiological and otherwise. In the Nuclear Operations Department, the Manager - Environmental and Radiation Control, and his staff function in a staff capacity to assist in the proper implementation of the Environmental Technical Specifications. Review of plant operations and the technical specifications shall be accomplished by the Plant Nuclear Safety Committee (PNSC) and the Corporate Nuclear Safety (CNS) Unit as organizationally described in Appendix A to the facility operating license. Independent off-site QA audits of plant operations shall be performed by the Operation & Maintenance (0&M) Unit as described in Appendix A to the facility operating license. Review and audit functions are defined as follows:
- a. Review by PNSC and CNS of proposed changes to the Environmental Technical Specifications and the evaluated impact of the change.
S-1 1335 198 APPENDIX B BSEP 1
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- b. Review bv FNSC and CNS of changes or modifications to plant systems or equipment which are determined by the General Manager to have a significant adverse effect on the environment and the evaluated impact of'the change.
- c. Review by PNSC and CNS of written procedures and changes thereto as described in Section 5.3.2 which are determined by the General l Manager to detrimentally affect the plant's environmental impact.
- d. Investigation by the PNSC of reported instances where an environ-mental protection limit is exceeded or the occurrence of an unusual environmental event associated with operation of the plant which involves a significant environmental impact. The report and recommendations that result from the PNSC investigation will be reviewed by the CNS.
- e. Corporate quality assurance audit of plant operations and written procedures for implementation of these Technical Specifications by O&M.
l 5.2 ACTION TO BE TAKEN IN THE EVENT OF AN ENVIRONMENTAL EVENT DURING PLANT OPERATIONS 5.2.1 An environmental event shall be reported promptly to the Vice President-Nuclear Operations and reviewed by the Plant Nuclear Safety Committee. The General Manager shall take action to abate any impact, immediately following his determination of appropriate action permitted by the technical specifications. 5.2.2 As specified in Section 5.4.2, a report of each environmental event shall be reviewed by the Plant Nuclear Safety Committee.
'.his report shall include an evaluation of the causa of the event, a record of the corrective action taken, and the recom-mendations for appropriate action to prevent or reduce the probability of a recurrence.
lhh BSEP 1 Appendix B 5-2
s 5.2.3 Copies of an auch reports shan be submitted to the Vice Preoident-Nuclear Operations and the Manager of Corporate Nuclear Safety and Quality Assurance Audit Section for review. 5.2.4 The circumstances of any environmental event shan be reported to the NRC as specified in Section 5.4.2. 5.3 OPERATING PROCEDURES 5.3.1 Written procedures shall be prepared and approved as specified in Section 5.3.2 for operation to ensure compliance with the environ-mental protection conditions and associated surveillance requirements of Sections 2 and 3. Proccdures win include sampling, analysis, and actions to be taken when environmental protection conditions are exceeded. Quality assurance procedures will be developed for monitoring, sample collection, and sample analysis. Testing frequency of any alarms will also be included. 5.3.2 Procedures described in Section 5.3.1 above, and changes thereto, determined by the General Manager to detrimentally affect the plant's environmental impact, shall be reviewed as specified in Section 5.1 and approved by the General Manager prior to implementation. Temporary changes to procedures which do not change the intent of the original procedure may be made, provided such changes are approved by two members of the plant management staff. Such changes shan be documented, and subsequently reviewed by the Plant Nuclear Safety Committee and approved by the General Manager prior to implementation as permanent procedure changes. 5.3.3 Procedures described in Section 5.3.1 above, and changes thereto, which are determined by the General Manager to not detri-mentally affect the plant's environmental impact shall be reviewed and approved by the General Manager or other member of the plant management staff designated by the General Manager prior to imple-mentation. 5.3.4 Written procedures shall be prepared and approved 1335 200 BSEP 1 Appendix B 5-3
og if milk samples collected 'over a calendar quarter chow average I-131 concentrations.of , 4.8 picoeuries per liter or greater, s. written report shall bc sub=1tted to the Director of the sp'propriare regional cffice (copy to the .
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. Director of Nucicar Reactor Regulation) within 30 days, and should include an evaluation of any release conditions, environmental fact' ors. or other aspects necessary to explain the ano=slous results. .
- c. Hincellsncour Reports (1) L' hen a change to the plant desirr, to the plant operation, or to the procedurcs described in Section 5.3 is pisnned which would have a significant adverse A.
, cffcet on.the tnvironment as dctormined by the General Manager or which involves l s.significant environmental matter or question not previously reviewed and evaluated by the :"RC, a report on the change shall be submitted to the NRC for information prior to impicmentation.
The report shall include descrip.tlon and evaluation of the impset of the change. (2) Request for changes. In Environmental Technical Specifications shall be submitted to the Director of Nuclear Reactor Regulation, NRC, for prior review and authorir.ation. The request shall include an evaluation s of the impset of the change. BSEP 1 Appendix B 5-7 133.5 201
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. . . . . . . . . : -- ~. . . .^~ ~ T CHAIRMAN OF T;iE BOARD PRESIDENT / CHI EF EXECUTIVE OFFICER OPERATIONS SeniorExecQicePres. ______,________,,
Chief Operating Officer l I I I POWER SUPPLY I AND I I CUSTOMER SERVICES Executive Vice Presicent l
. I I
I I POWER SUPPLY l Senior Vice Presicent 1 I I I NUCLEAR OPERATIONS NUCLEAR SAFETY l DEPARTi!ENT 'AND : RESEARCH Vice Presicent Vice President g 1 1 1 I NUCLEAR OPERATIONS CORPORATE NUCLEAR SAFETY I DEPARTMENT AND - 1
's QUALITY ASSURANCE AUDIT J 3 f f, s , . . Manager
\ l
\ l
\
l I Plant i General Hanager i 1335 202 Plant Nuclear Safety
- Responsible for performance Committee and monitoring of Fire Protection Program.
HAhAGEHINT ORGANIZATION CHART BRUNSwlCK - UNIT I F1GURE 5.1-1 Appendix B
~~
6.0 ADMINISTRATIVE CONTROLS g 6.1 RESPCNSIBILITY . 6.1.1 The General Manager shall be responsible for overall facility l operation and shall delegate in writing the succession to this responsi-oility during his absence. 6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support snall be as shown on Figure 6.2.1-1. FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figures 6.2.2-1 7.e 6.2.2-2 and:
- a. Each on duty shift shall be compased of at least the minimum shift crew composition shown in Table 6.2.2-1.
- b. At least one licensed Operator shall be in the control room for each riactor containing fuel,
- c. At least two licensed Operators shall be present in the control room for each reactor in .the process of start-up, scheduled reactor shutdown and during recovery from reactor t ri ps ,
- d. an individual qualified to implement radiation protection procedures shall be on site when fuel is in either reactor,
- e. All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent respon-sibilities during this operation,
- f. A e Brigade of at least five members shall be maintained ons s at all times. The Fire Brigade shall not include the minimum Shift crew shown in Table 6.2.2-1 or any personnel requiref .cr other essential functions curing a fire emergency.
1335 203 BRUNSWICK-UNIT 2 6-1
CHAIRMAN OF THE BOARD PRESIDENT / CHIEF EXECUTIVE OFFICER OPERATIONS SeniorExecyicePres. ________________, Chief Operating Officer l 1 l 1 POWER SUPPLY l 3 AND CUSTOMER SERVICES
- cutive Vice Presloent ;
1 I I I POWER SUPPLY l Senior Vice Presicent l 1 I I I NUCLEAR OPERATIONS- NUCLEAR SAFETY DEPARTMENT l AND i RESEARCH Vice President Vice President ! I I I NUC. EAR OPERATIONS CORPORATE NUCLEAR SAFETY I DEPARTMENT AND I 3 ff \ QUALITY ASSURANCE AUDIT J
- s ,. Manager
\ i
\ '
I, i Plant i General J Manager s l Plant Nuclear Safety
- Responsible for performance Comm,ttee i 1333 204 and monitoring of Fire MANAGEMENT ORGANIZATION CHART BRUNSWlCK - UNIT 2 FIGURE 6.2.I-1
~
6-2
i* i GENERAL MANAGER BRUNSWICK PLANT E {n HANAGER MANAGER MANAGER C DR N OPERATIONS MAINTENANCE fDM AllVE AND QUAL. A HANCE e i
"" OPERATIONS ADMINISTRATIVE SPECIALIST SPECIALIST
$HIFT OPERATING {ND RANylR0fe4ENig ENGINEERING SPECIALIST SUPE SORS ENGINEERS SUPERVISOR t SUPERylSOR SECURITY FIRE PROTECTION f OL M REGULATORY l
! +
4 SHIFT PLANT PLAET STORES PROJECT SUPERYlSOR
!e FORElfM SERVICES OFFICE FOREMEN ENGINEERS SUPERVISOR QUALITY d, SRO FOREMAN SUPERVISOR TRAINING ASSURANCE SENIOR COST CONTROL SPECIALIST SPECIALIST DOCLNENT ENGINEERS CONIROL '
OPERAT0els SR0 CONTROL CONTROL 'I OPERATORS - R0 e
! AUXILIARY HECHAN CAL 1 8 C. SPECIALIST SPECIALIST SPECIAllSit s' OPERATOR A MAINTEN NCE HAINIENANCE ALARA NEALTH PHYSICS TRAINING j SUPERV1SOR SUPERV1SOR a
HECitANICAL ELECTRICAL . l .8 C." SPECIALIST FOREMEN CA 04 ENGINEERS FORD 4 Ell CHEMISTRY R SPECIALISTS SPECIALISTS FOREMEN gOMTRgifiI FOREHEN D ST QUALITY CONTROL .tURVEILLANCE U i LTi j J
,N LEGEND ENGINEERS O SRO-SENIOR REACTOR OPERATOR LICENSE E FACILITY ORGARlZAT10ll R0-REACIOR OPERATOR LICENSE FIGURE 6.2.2-1
~~
T .
~
.__.~ __~_ ~~~_
PLANT GENERAL MANAGER , , DIRECTOR Nuclear Saf ety anc Quality Assurance SUPERVISOR SPEClALiSTS SUPERVIS0R Quality Fire Protection Training Assurance FIRE PROTECTION FIRE PREVENTION SUPPORT GROUP COMMITTEE BRIGADE FIRE CHIEF * (EMERGENCY COORDIN ATOR) SHI FT FI RE BRIGADE
- Number of Brigace Fi re Chief s varies with shif t organization
** One Specialist is assigned the cuties of the p'lant fire chief
. FIGURE 6.2.2-2 BRUNSWICK - UNIT 2 _
s-n 133b 206
A0!il!!!STRATIVE CO::TROLS I 5.3 FACILITY STAFF 00ALIFICATIC::S 6.3.1 Each member of the facility staff shall meet or exceed the mini-t:um qualifications of ANSI N18.1-1S?1 for comparable position, except for the Environmental and Radiation Control Supervisor who shall meet or exceed the qualifications of Regula:ory Guide 1.8, September 1975. l 6.4 TRAIN!! G 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Supervisor and shal'1 meet or exceed the requirements and recommtndations of Section { 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55. 6.4.2 A training program fnr the Fire Brigade shall be maintained under the cirection of the Plant Fire Chief and snall meet or exceed the require-ments of Section 27 cf the NFPA Code-1975. 6.5 REVIEW AND A'JDIT 6.5.1 PLA!!T NUCLEAR SAFETY C0f4MITTEE (PNSC) - FU:: TIO:. 6.5.1.1 ine P:;5C snall function to advise the General Manager on all matters related to nuclear safety. [ C0:4P05IT10:: 6.5.1.2 ine PNSC shall be composed of the: Chairman: Plant General Manager Vice Chairman: Operations Manager, Maintenance Manager, Technical-Administrative Manager, or Director-Nuclear Safety and QA Secretary: Arhinistrative Supervisor Member: Maintenance Supervisor (I&C) Member: Maintenance Supervisor (Mechanical) Member: Engineering Supervisor Member: Environmental and Radiation Control Supervisor . Member: Quality Assurance Supervisor Member: Shift Operating Supervisors Member: Training Supervisor ALTERNATES 6.5.1.3 All alternate memoers shall be appointed in writing by the PNSC Chairman.to serve on a temporary basis; however, no more than two alternates any one time. shall participate as voting members in PNSC activities at BRUNSWICK-UNIT 2 6-6 133b ,07 2
ADMI:;'STRATIVE CONTRO:.5 MEETING FREQUENCY 6.5.1.4 Tne PNSC shall meet at least once per calendar month and as convened by the PNSC Chairman or his designated alternate. 000 RUM 6.5.1.5 A quorum of the PNSC shall consist of the Chairman or Vice Chairman and three members including alternates. I RESPONSIBILITIES 6.5.1.6 The PMSC shall De responsible for:
- a. Review of 1) all procedures required by Specification 6.3 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the General Manager to affect nuclear safety. l
- o. Review of all proposed tests and experiments that affect nuclear safety.
- c. Re, view of all proposed changes to Technical Specifications.
- d. Review of all proposed changes or mooifications to plant systems ,or equipment that affect nuclear safety.
- e. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President - Nuclear Operations and to the Managcr - Corporate Nuclear Safety and Quality Assurance Audit,
- f. Review of all events requiring 24 hour notification to the Commission,
- g. Review of facility operations to-detect potential safety hazards.
- h. Performance of special reviews, investigations cad reports thereon 6s requested by the Manager - Corporate Nuclear Safety and Quality Assurance Audit.
f BRUNSWICK-UMJr 2 67
r, - ' -' *~~ ~
. _ _ _ . _ _ _ ~._ - - - - T~
- g. AOMI:llSTRATIVE COGTROLS ,
jRESP0!SIBILITES(Contnued) i p -
, , i.
Review of the Plant Seurity Plan and implementing procedures. j. Review of the Emergency Plan and implementing procedures. t AUTHORITY 6.5.1.7 The PilSC shall:
- a. Recommeno to the General & > -" written approval or disapproval I of items considered under C a) th'Sugh (d) aoove. ,
- b. Ronder determinations in writ ng with regard to whether cr not i
eacn item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.
, c. Provide written notification within 24 hours to the Vice President-
- j. Nuclear Operations and the Manager - Corporate Nuclear Safety ni ! Quality Assurance Audit of disagreement between the IMSC and the General Manager; however, the General Manager shall have responsibility for resolution of such
[, disagreements pursuant to 6.1.1 above. RECORDS 1 6.5.1.8 The Pt:SC shall maintain wr.tten minutes of each meeting and copics sha'l be provided to the Vice President-Nc.J. ear Operations and to the Manager - Corporate fiuclear Safety. and Quality Assurance Audit. I i 1335 209 I l Brut:SWICK-U,41T 2 68 I
.l- AIX41N1ST.MTIVE CONTROLS
- )
16 6.5.1 Corporste Nuclear Safety 6 Ouality Assurance Audit Section (CNS 6 OAASh
)
i i Responsibility l i
!' \
s 6.5.2.1 The Manager - Corporate Nuclear Safety & Quality Assurance Audit under the Vice President-Nuclear Safety and Research is charged I with the overall responsibility for administering the independent i off-site revt 2v and quality assurance audit programs as follows: l
- a. pproves selection of the individual (s) to conduct off-site safety reviews and quality cssurance audits.
- b. Has access to the plant operating records and operating personnel in performing the independent reviews and quality assurance audits.
I L
- c. .. Prepares and retains written records of reviews and f
', audits.
I I
- d. Assurcs independent safety reviews are conducted on all l items required by Section 6.5.3.3 and quality assurance I
l audits cover all the items included in Section 6.5.4.1.
! e. Distributes reports and other records to appropriate managers.
i 1 6.5.3 Cornc rate Nucicar Saf etv Unit ) ) l Function 1 BRUNSWICK-UNIT 2 6-9
- - - - - . .. > s AIMINISTRATIVE CONTROLS 6.5.3.1 The Corporate Nuclear Safety Unit of the Corporate Nuclear Safety & Quality Assurance Audit Section shall provide independent off-site review of significant plant changes, tests, L d procedures; verify that reportable occurrences are promptly investigated and corrected in a manner which reduces the probability of recurrence of such events; and detect trends which may not be apparent to a day-to-day observer. Personnel 6.5.3.2
- a. Person:e1 assigned responsibility for independent reviews shall be pecified in technical disciplines, and shall collec-tively have the experience and competence required to review problems in the following areas:
- 1. Nuclear power plant operations
- 2. Nuclear engineering "3. Chemistry and radiochemistry
- 4. Metallurgy
- 5. Instrumentation and control
- 6. Radiological safety
- 7. Mechanical and electrical engineering
- 8. Administrative controls
- 9. Seismic and environmer :al
- 10. Quality assurance practices
- b. The following minimum experience requirements shall be es-stablished for those persons involved in the independent off-site safety review program:
BRUNSWICK-UNIT 2 6-10 1335 211
._ t __ t__-.
' ADMINISTRATIVE CONTROLS
- 1. Ifanager of CNS & QAAS - Bachelor of Science in engineering or related field and ten (10) years related experience including five (5) years involvement with operation and/or design of nuclear power plants.
- 2. Reviewers - Bachelor of Science in engineering or related field or equivalent and five (5) years related exp= pence including three (3) years involvement with operation and/or design of nuclear power plants.
- c. An individual may possess competence in more than one specialty area. If sufficient expertise is not available within the Corporate Nuclear Safety Unit, competent individuals from other CP&L organizations or outside consultants shall be utilized in performing independent off-site reviews and investigations.
- d. At least three persons, qualified as discussed in Specifica-tion 6.5.3.2.b, will review each item submitted under the
, .. requirements of 6.5.3.3.
- e. Independent safety reviews shall be perfo'rmed by personnel not directly involved with the activity or responsible f or the activity.
Subjects Reouirinc Independent Review 6.5.3.3 The f ollowing subjects shall be reviewed by the Corporate Nuclear Safety Unit: i 6-11 177c 9,9 i BRUNSWICK-UNIT 2 IJJ3 0IC
_r _ _ _ .
. ADENISTRATIVE CONIR01.S
- a. Written safety evaluations of changes in the facility as described in the Safety Analysis Report, changes in procedures as described in the Safety Analysis Report and tests or experi-ments not described in the Safety Analysis Report which are completed without prior NRC approval under the provisions of 10 CFR 50.59(a)(1). This review is to verify that such changes, tests, or experiments did not involve a change in the technical specifications or an unreviewed safety question as defined in 10 CFR 50.59(a)(2).
b. Proposed changes in socedures, proposed changes in the facility, or proposed tests or experiments, any of which involves a change in the technical specifications or an unreviewed safety ques-tion pursuant to 10 CFR 50.59(c) . Matters of this kind shall be referred to the Corporate Nuclear Safety Unit by the Plant Nuclear Safety Committee following its review, or by ,other functional organizational units within Carolina Power & Light Company (CP&L) prior to implementation.
- c. Changes in the technical specifications or license amendments relating to nuclear safety prior to implementation, except in those cases where the change is identical to a previously reviewed proposed change.
- d. Violations, deviations and reportable events, which require reporting to the NRC within 24 hours, and as defined in the plant technical specifications such as:
- 1. Violations of applicable codes, regulations, orders, technical specifications, license requirements or internal procedures or instructions having safety significance; and
~
BRUNSWICK-UNIT 2
~
. A3:ttNISTW. TIVI COI*IROLS
- 2. Significant operating abnormalities or deviations f rom normal or expected performance of plant saf ety-related structurcs, systems, or co=ponents.
Review of events coverud under this paragraph shall
- include the results of any investigations made and the rutemmendations resulting from such investigations to prevent or reduce the probability of recurrence of the 6
ev en t.
- e. Any other mat:er involving safe operation of the nucicar power plant 'thich the Manager - Corporate Nuc1 car Saf ety
& Quality Assurance Audit Section dee=s appropriate for consideration, or which is referred to the Manager -
Corporate Nuclear Safety & Quality Assurance Audit Section by the onsite operating organization or by other functional organizational units within~ Carolina Power & Light Conpany. Follow-un Action 6.5.3.4 Results of Corporate Nuclear Safety (CNS) revicus, including recommendations and concerns will be documen'.cd.
- n. Copies of the documented review will be retained in the Corporate Nuclear Safety & Qutlity Assurance Audit Section f iles.
b. Recommendations and concerns wi.'.1 be submitted to the Vice President - Nuclear Operations within 14 days of determination.
- c. A summation of Corporate Nuclea: Safety recommendations and concerns sill be submitted to the President / Chief Executive BRUNSWICK-UNIT 2 6-12a 1335 214
~ -- - - - - - . - - _ .. ADMINISTRAT WC 0!.TEOLS ,
. . ~ . .- . .. .
'; Officer; Senior Executive Vice President and Chief Operating Officer; I ;! Executive Vice President-Power Supply and Customer Services; Senior il 'i. Vice President-Power Supply; Vice President-Nuclear Safety and l
Rasearch; Plant General Manager; and others, as appropriate on at least a hi-monthly frequency. 6.5.3.5 The Corporate Nuclear saf ety Unit review progra= shall be conducted in accordance with written, approved procedures. 6.5.4 caeration & Maintenance Unit
't Function I
6.5.4.1 The Operation & Maintenance Unit of the Corporate Nuclear I l tafety & Quality Assurance Audit Section shall perform audits of plant activities. These audits shall encompass:
- a. The conf ormance of facility operation to all provisions
. contained within the Technical Specifications and applicable license conditions at least once per year.
- b. The training and qualifications of the entire facility l staff at least once per year.
l
- c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or method of operation that affect nucicar safety at least once per six months.
- d. The verification of compliance and implementation of the requirencnts of the Quality Assurance Program to meet the
, criteria of Appendix "B",10 CFR 50, at least once per I
two years. BRUNSWICK-UNIT 2 6-12b j } };525
A7fTNT9TRATTVe CONTROLS _
~
- e. The Emergency Plan and implamenting procedures at least once per two years.
- f. The Security Plan and implementing procedures at least once per two years.
- g. The Facility Fire Protection Program and implementing procedures at least once per two years.
- h. Any other area of facility operation considered appropriate by the Corporate Quality Assurance Audit Operation & Main-tenance Unit, the Executive Vice Presidant-Power Supply and Customer Services, or the Senior Vice President-Power Supply.
Personnel 6.5.4.2
- a. Audit personnel will be independent of the area audited.
Selection for auditing assignments is based on experience or training which ests'alishes that their qualifications are commensurate with the complexity or special nature of the ac-
, .,tivities to be audited. In selecting auditing personnel, consideration will be given to special abilities, specialized technical training, prior pertinent experience, personti characteristics, and education.
- b. Qualified outside consultant; or cther individuals independent from those personnel directly involved in plant operation, but within the Operations Groups will be used to augn.ent the audit teams when necessary. ,
1335 216 BRUNSWICK-UNIT 2 6-12e
AD".lulSTRATIVE CD:.TROLS couvrte 6.5.4.3 Results of audit are approved by the Manager - Corporate Nuclear Safety & Quality Assurance Audit Section and transmitted directiv to the Company President / Chief Executive Officer, the Senior Executiv: Vice President and Chief Operating Officer, the Executive Vice President-
! h wer Supply and Customer Services, the Senior Vice President-Power Supply, and the Vice President-Nuclear Safety and Research, and others as appropriate, within 30 days after the completion of the audit.
6.5.4.4 The corporate quality assurance audit progrcm shall be conducted in accordance with written, approved procedures. 6.5.5 0UTSIDE AGENCY IN5pECT]ON AND AUDIT PROGRAM 6.5.5.1 An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 montns ut1}lizing an outside fire protection firm. 6.5.5.2 An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at l least once per 36 months. BRUNSWICK-UNIT 2 6-13 - 1335 217
A:M":STRA7!'!E CoriTROLS I f
; 6.6 0 0RTA3LE OCCURREt:CE ACTIO:1 1
6.6.1 The following actions shall De taken for REPORTABLE OCCURRENCES:
, a. The Commission shall be notified and/or a report submitted
; pursuant to the requirements of Specification 6.9.
- b. Each REPOR1ao'.E OCCURREfCE requiring 24 hour notification to the Commissi.sn shall he reviewed by the PNSC and submitted tn j Manar,er - Corporate Nuclear Safety and Quality Assurance Audit and the Vice President-Nuclear Operations.
6.7 SAFtTY Liti!T VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
- a. The facility shall be placed in at least HOT SHU'i10Wr within tWo hours,
- b. The Safety Limit ... tion shall be reported to the Commission, the Vice President-Nuclear Operations, and to the Manager-Corporate
.:uclear Sa fety and Quality Assurance Audit within 24 hours.
- c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PflSC. This report shall describe (1) applicable circumstances preceding the violatian, (2) effects of the violation upon facility components, systems or struc-l tures, and (3) corrective action tak m to prevent recurrence.
- d. The Safety Limit Violation Report sha'il be submitted to the
{ Commission, tne fianager - Corporate Nuclear Safety and Quali:y Assurance Audic,and the Vice President-Nuclear Operations within 14 days. of the violation. 6.8 PROCEDURES 6.c.1 Written procedures shall be established, implemented and main-tained csvering :ne ac. ities referenced below:
- a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November,1972.
- b. Refueling operations,
- c. Surveillance and test activities of safety related equipment.
- d. Security Plan implementation.
- e. ' Emergency Plan implementation,
- f. Fire Protection Program implementation.
6-14 BRUNSWICK - UNIT 2
} 33f) 2}8 . ~ .._ ___. - _ _ _ . . .. -
ADM*NISTRATIVE CCKTROLS PROCEDURES (Continued) 6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the PNSC and approved by the General Manager prior to imple- [ menta-ion and reviewed periodically by the PNSC as set forth in ac=in-istrative procedures. 6.8.3 Temporary changes to procedures of 6.8.1 above may be ma 'a proviced:
- a. The intent of the original procedure is not altered.
- b. The change is approved by two members of the plant management staff, at least one of wnom holds a Senior Reactor Operator's License on the Brunswick Plant.
- c. The change is documented, reviewed by the PNSC and approved by the General Manager within 14 days of implementation.
l 6.9 REPORTINC REOUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES , 6.9.1 In addition to the applicable reporting requitements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted. STARTUP REPORT .
' l 6. 9.1.1 A summary report of plant startup and power escalation testin
; shall be submitted following (1) receipt of an operating license, (2) g h awandment to the license involving a planned increase in power level, P (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.
The startup report shall address each of the tests identified in the
, FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test. pro-gram and a comparison of these values with design precictions and specifications. Any corrective actions that were required to obtain satisfactory coeration shall also be described. Any additional specific details required in license conditions based on other cc=mi:-
ments shall be included in this reocrt. 6.1.1.3 Startuo reports shall be submitted within (1) 90 days follew-ing completion of the startup test program, (2) 90 days following re-sumption or commencement of cannercial power operation, or (3) 9 months following ini-ial criticality, whicnever is earliest. If the Star:ue
,, Report coes not cover all three events (i.e. , initial criticali y,
' BRUNSWICK - UNIT 2 6-15 1335 219
~
- ~ ~~
. _ . _ ._.. ...___-~ 1 .
. ADMINISTRATIVE CONTROLS .
RECORD RETENTIJN (Costinued) _ _..
- h. Records of annual physical inventory of all sealed source material of record.
6.10.2 The following records shall be retained for the duration of the Facility Operating License:
- a. Records and drawing changes reflecting facility design modifi-cations made to systems and equipment described in the Final Safety Analysis Report.
- b. Records of new and < radiated fuel inventory, fuel transfers and assembly burnup nistories,
- c. Records of facility radiation and contamination surveys.
- d. Records or radiation exposure for all individuals entering radiation control areas.
- e. Records of gaseous and liquid radioactive material released to the environs,
- f. Records of transient or operational cycles for those facility components identified in Table 5.7.1-1.
- g. Records of reactor terts and experiments.
- h. Records f training and qualification for current members of the plant staff.
- i. Records of in-service inspections performed pursuant to these Technical Specifications.
- j. Records of Quality Assurance activities required by the QA Manual.
- k. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
)* Records of meetings of the PNSC and of the previous off-site review organization, Company Nuclear Safety Committee (CNSC).
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure. BRUNSWICK - UNIT 2 6-20 1335 220
Obiective This section describes the administrativt controls and procedures necessary to implement the Environmental Technical Specifications. 5.1 ORGANIZATION AND REVIEW The General Manager is directly responsible for the safe operation of the l facility as shown in Figure 5.1-1. In all matters pertaining to the operation of the plant and to the Environmental Technical Specifications, , the General Manager is directly responsible to the Vice President - Nuclear Operations. The Environmental and Radiation Control Supervisor is responsible to the General Manager for all Environmental Technical Specifications applicable to the plant, rar ;1ogical and otherwise. In the Nuclear Operations Department, the .: nager - Environmental and Radiation Control, and his staff function in a staff capacity to assist in the proper implementation of the Environmental Technical Specificaricus. Review of plant oper.stions and the technical specifications shall be accomplished by the Plant Nuclear Safety Committee (PNSC) and the Corporate Nuclear Safety (CNS) Unit as organizationally descriced in Appendix A to the facility operating license. Independent off-site QA audits of plant operations shall be performed by the Operation & Maintenance (0&H) Unit as described in Appendix A to the facility operating license. Review and audit functions are defined as follows:
- a. Review by PNSC and CNS of proposed changes to the Environmental Technical Specifications and the evaluated impact of the change.
1335 221 5-1 _. APPENDIX B ESEP 2
- b. Review by PNSC and CNS of changes or modifications to plant systems or equipment which are determined by the General Manager to have a wignificant adverse effect on the environment and the eval.uated impact of the change.
- c. Rariew by PNSC and CNS of written procedures and changes thereto as described in Section 5.3.2 which are determined by the General l Manager to detrimentally affect the plant's environmental impact.
- d. Investigation by the *NSC of reported instances where an environ-mental protection limit is exceeded or the occurrence of an unusual environmental event associated with operation of the plant which involves a significant environmental imps 2t. The report and recommendations that result from the PNSC investigation will be reviewed by the CNS.
- e. Corporate quality assurance audit of plant operations and written procedures for implementation of these Technical Specifications by O&M.
l 5.2 ACTION TO BE TAKEN IN THE EVENT OF AN E!WIRONMENTAL EVENT DURING PLANT OPERATIONS 5.2.1 An environne. ital event shall be reported promptly to the Vice President-Nuclear Operations and reviewed by the Plant Nuclear Safety Committee. The General Manager shall take action to abate any impact, immediately following his determination of appropriate action pernitted by the technical specificatiens. - 5.2.2 As specified in Section 5.4.2, a report of each environmental event shall be reviewed by the Plant Nuclear Safety Committee. This report shell include an evaluation of the cause of the event, a record of the corrective action taken, and the recom-mandations for appropriate action to pravent or reduce the probability of a recurrence. 1335 222 BSEP 2 Appendix B 5-2
5.2.3 Copies of au such reports shan te submitted to the Vice President-Nucler.r Operations and the Manager af Corporate Nuclear Safety and' Quality Assurance k!.it Section for review.
, 5.2.4 The circumstmices of any environmental event shan h i reported to ::he NRC as specified in Section 5.4.2; 5.3 OPERATING PROCEDURES 5.3.1 Written procedures shall be prepared and approved as specified in Section 5.3.2 for operation to ensure compliance with the environ-mental protection conditions and associated surveillance requirements of Sections 2 and 3. Procedures will include sampling, analysis, and actions to be taken vnen environmental protection u .ditions are exceeded. Quality assurance procedures will be devcloped for monitoring, sample conection, and sample analysis. Testing frequency of any alarns will also be included.
5.3.2 Procedures described in Se: tion 5..%1 above, and changes thereto, determined by the General Manager to detrimentally affect the plant's environa stal impact, shan be reviewed as specified in Section 5.1 and approved by the General Manager prior to implementation. Temporary changes to procedures which do not change the intent of the original procedura may be made, provided such changes are approved by two members of the plant management staff. Such changes shall be documented, and subsequently reviewed by the Plant Nuclear Safety Committee and approved by the General Manager prior to implementation as permanent procedure changes. 5.3.3 Procedures described in Section 5.3.1 above, and changes thereto, which are determined by the General Manager to not detri-mentally affect the. plant's environmental impact shall be reviewed and approved by the General Manager or other member of the plant management staff designated by the General Manager prior to imple-mentation. 5.3.4 Written procedures shall be prepared and approved 1335 223 BSEP 2 Appendix B 5-3
- - - - - = .. _ _ _ _ . _ _ _ _ ,
;,.mg If milk samples collected over a calendar quarter chev sverste I-131 concentrations of ,
4.8 picoeuries per liter or greater, s.uritten . report shs31 be submitted to the Director of the sp' pros riate regional of fice (copy to the . Director cf Nucle:r Reactor Regulation) within 30 dsys, and should include an evaluation of any release conditions, environmental factors or other aspects necessary to cxplsin the anomalous
* ~
results.
- c. MLncellencour Renorts (1) k' hen a change to the plant design, to the plant operation, or to the procedures dencribed in Section 5.3 is pisnned, which would have a significant adverse 9D4. .
effcet on the environment as determined by the General hger or which involves o significant environmental matter or question not previously revic cd and cvaluated by the :"RC, a report nn the change shall be submitted to the NRC for information prior to impicmenta: ion. The report shall include descrip.tlon and evaluation of the impset of the chance. (2) Request for changes. in Environmental Technical Specifiestions shall be submitted to the Director of Nuc1 car Rcsetor Regulation, NRC, for prior review and authorization. The request shall include an evaluation of the impset of the change. BSEP 2 Appendix B ' 5-7
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CHAIRMAN OF THE BOARD PRESIDENT / CHIEF EXECUTIVE OFFICER OPERATIONS SeniorExecJicePres. ________________, Chief Operating Officer l I I l P0hLR SUPPLY I AND ' CUSTOMER SERVICES ' Executive Vice Presicent. g i i i i POWER SUPPLY I Senior Vice Presicent I i i i l I NUCLEAR OPERATIONS- ' NUCLEAR SAFETY , DEPARTMENT AND i Vice Prei,1 cent RESEARCH i Vice Presicent i i l I i HUCLEAR OPERATIONS' CORPORATE NUCLEAR SAFETY I DEPARTMENT AND - 1 3 ,fg 's QUALITY ASSURANCE AUDIT -I s , . . Manager N i
\ I
\ l i
Plant i
.J General Manager i
Plant Huclear setetr 1335 225
- Responsible for performance Comm.ttee i and monitoring of Fire Protection Program.
E20NSWICK - UNIT 2 F1GURE 5.1-1 Appendix B _ . .}}